S. Carusotti , R. Lombroni , M. Scarpari , M. Notazio , A. Pizzuto , F. Crisanti , P. Fanelli , G. Calabrò
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引用次数: 0
Abstract
The main aim of this study is to explore a conceptual Alternative Magnetic Layout (AML) for the future nuclear fusion reactor based on the Tokamak concept. The proposed concept is eventually applied as a large down scaled study for the new academic tokamak Tuscia Research University Small Tokamak (TRUST), under construction at University of Tuscia (UNITUS). In this proposal the Central Solenoid (CS) placed around the Toroidal Field (TF) coils providing a relevant reduction in the reactor radial build. In order to compensate the increase of the toroidal filed on the coils, that it is intrinsic in such proposal, High Temperature Superconductor (HTS) material is foreseen for the TF coils. An overview of the proposed design and a possible plasma scenario is presented showing the AML advantages and disadvantages. The electromagnetic and structural characterizations for a preliminary design of the TF coils system is included in this paper to prove the engineering feasibility of the solution. Moreover, the involvement of the AML design in the TRUST project framework is presented. TRUST is a flexible and low-cost university-class experiment, to train the next generation of fusion engineers and physicists. Beyond its academic goal, TRUST is designed to allow easy replacement of the plasma facing components and testing innovative technologies (i.e., meta-materials) and materials including a feasible upgrade the magnetic system from copper to HTS.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.